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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20211D1321999-08-20020 August 1999 Application for Amend to License DPR-50 to Revise TS Bases Re Degraded Undervoltage Relay Setpoint Calibration Frequency & Degraded Voltage Relay Tolerance Rev ML20210J0941999-07-29029 July 1999 Suppl TS Change Request 274 to License DPR-50,revising ESF Sys Leakage Limits in post-accident Recirculation Surveillance Tss,As Result of NRC Generic Concerns Re CR Habitability Issues ML20196K5901999-06-29029 June 1999 LAR 285 for License DPR-50,clarifying Authority in Encl License Pages to Possess Radioactive Matls Without Unit Distinction,So That After Transfer of TMI-1 License to Amergen,Radioactive Matls Can Continue to Be Moved ML20209C0551999-06-29029 June 1999 LAR 77 for License DPR-73,clarifying Authority in Encl License Pages to Possess Radioactive Matls Without Unit Distinction,So That After Transfer of TMI-1 License to Amergen,Radioactive Matl May Continue to Be Moved ML20195E3341999-06-0404 June 1999 TS Change Request 265 to License DPR-50,modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20209B5891999-05-26026 May 1999 LAR 281 to License DPR-50,revising TMI-1 UFSAR Chapters 5 & 14 to Permit Use of Conservative Deterministic Failure Margin Methodology for Seismic Analysis of Portions of Auxiliary Steam Line.Rept 240046-R-001 Encl.Rept Withheld ML20206R1111999-05-13013 May 1999 Application for Amend to License DPR-50,requesting That License Sections 2.a.(3) & 2.c.(7) & TS Section 3.1.1 Be Revised to Incorporate Administrative Updating & Changes to Bases Statement ML20205H0691999-04-0101 April 1999 TS Change Request 262 to License DPR-50,revising TS by Adding LCO Action Statements & Making SRs More Consistent with NUREG-1430,correcting Conflicts or Inconsistencies Caused by Earlier TS Revs & Revising SFP Sampling ML20203B0421999-02-0202 February 1999 TS Change Request 274 to License DPR-50,expanding Scope of Systems & Test Requirements for post-accident RB Sump Recirculation ESF Systems & Increasing Max Allowable Leakage of TS 4.5.4 for Applicable Portions of ESF Systems ML20196G4401998-12-0303 December 1998 LAR 278 to License DPR-50,requesting Consent to Transfer & Authorize Amergen to Possess,Use & Operate TMI-1 Under Essentially Same Conditions & Authorizations Included in Existing License.Supporting Documentation,Encl ML20196H9751998-12-0303 December 1998 LAR 279 to License DPR-50,reflecting Decrease in RCS Flow Resulting from Revised Analysis to Allow Operation of Plant with 20% Average Level of SG Tubes Plugged Per SG ML20196G7671998-11-25025 November 1998 TS Change Request 277 to License DPR-50,changing Surveillance Specs for OTSG ISIs for TMI-1 Cycle 13 RFO Exams Which Would Be Applicable for One Cycle of Operation Only ML20154Q6201998-10-19019 October 1998 TS Change Request 248 to License DPR-50,adding Operability & SRs for Remote Shutdown Sys Similar to Requirements in NUREG-1430, Std Tech Specs - B&W Plants, Section 3.3.18, Remote Shutdown Sys ML20154P8441998-10-19019 October 1998 Application for Amend to License DPR-50,providing Allowable RCS Specific Activity Limit Based on OTSG Insp Results Performed Each Refueling Outage.Proprietary & non- Proprietary Calculation,Encl.Proprietary Info Withheld ML20154M3691998-10-15015 October 1998 Application for Amend to License Amend Request 276 to License DPR-50 Revising UFSAR Chapter 14 Accident Analysis Atmospheric Dispersion Factors.Ufsar Revised Pages Encl ML20249B2391998-06-11011 June 1998 TS Change Request 273 to License DPR-50,incorporating Alternate High Radiation Area Control Consistent W/Reg Guide 8.38 ML20217E5131998-03-23023 March 1998 Application for Amend to License DPR-50,revising TS Section 3.1.2 to Incorporate New Pressure Limits for Reactor Vessel IAW 10CFR50,App G for Period of Applicability Through 17.7 Efpy.Request Also Submitted in Response to NRC ML20217G0161997-10-0303 October 1997 Suppl to License Amend Request 268 to License DPR-50, Replacing Pages 4-80 & 4-81 Previously Submitted w/TMI-1 License Amend Request 268 on 970812 ML20211C3211997-09-19019 September 1997 Supplemental Application for Amend to License DPR-50 Re License Amend Request 269 Submitted on 970814.Suppl Includes Addl Change to TS Section 3.1.4 & Proposed Page Rev Clarifying That UFSAR Analysis Is More Conservative ML20211C2221997-09-19019 September 1997 Supplemental Application for Amend to License DPR-50 Re TS Change Request 266.Supplement Provides for Phased Review & Issuance of License Amends & Involves Administrative Correction to TS Decay Heat Removal Sys Leakage Rate ML20210J9951997-08-14014 August 1997 Revised License Amend Request 269 for License DPR-50, Revising TMI-1 UFSAR Section 14.1.2.9 Environ Dose Consequences for TMI-1 Steam Line Break Analysis ML20141J3981997-08-12012 August 1997 Tech Spec Change Request 268 for License DPR-50,revising Surveillance Specification for Once Through Steam Generator Inservice Insp for TMI-1 Cycle 12 Refueling (12R) Exams Applicable to TMI-1 Cycle 12 Operations ML20198E7871997-07-30030 July 1997 TS Change Request 266 to License DPR-50,incorporating Addl Sys Leakage Limits & Leak Test Requirements for Systems Outside Containment Which Were Not Previously Contained in TS 4.5.4 ML20141E1311997-05-0808 May 1997 Application for Amend to License DPR-50,consisting of Change Request 264,incorporating Addl NRC-approved Analytical Methods Used to Determine TMI-1 Core Operating Limits ML20140E2351997-04-21021 April 1997 Application for Amend to License DPR-50,requesting Rev to TS 3.3 Re Emergency Core Cooling,Reactor Bldg Emergency Cooling & Reactor Bldg Spray Systems ML20134M1111997-02-0707 February 1997 Application for Amend to License DPR-50,incorporating Certain Improvements from Revised STS for B&W Plants, NUREG-1430 & Addl Changes as Described in Encl TS ML20133D2651996-12-24024 December 1996 Application for Amend to License DPR-50,requesting Reinstatement of Auxiliary & Fuel Handling Bldg Ventilation Sys TS ML20132F3221996-12-16016 December 1996 Application for Amend to License DPR-50,consisting of Change Request 260,reflecting Change in Legal Name of Operator of Plant from Gpu Corp to Gpu Inc & Reflecting Plant License & TS Registered Trade Name of Gpu Energy ML20135C5201996-12-0202 December 1996 TS Change Request (Tscr) 75 to License DPR-73,relocating Audit Frequency Requirements to Pdms QA Plan ML20117H0181996-08-29029 August 1996 Application for Amend to License DPR-50,consisting of TS Change Request 257,incorporating Certain Improvements from STS for B&W Plants (NUREG-1430) ML20113D1901996-06-28028 June 1996 Application for Amend to License DPR-50,consisting of Change Request 259,allowing Implementation of Recently Approved Option B to 10CFR50,App J ML20112C8751996-05-24024 May 1996 Errata to Application for Amend to License DPR-50,consisting of TS Change Request 243,replacing Pages for App a ML20101R1361996-04-10010 April 1996 Application for Amend to License DPR-50,consisting of Change Request 243,revising Addl Group of Surveillances in Which Justification Has Been Completed Following Receipt of 930623 Application ML20100J6831996-02-22022 February 1996 Application for Amend to License DPR-50,consisting of Change Request 254,revising Proposed TS Page 4-46 on Paragraph 4.6.2 That Provides Addl Testing Requirements in Case Station Battery Cell Parameters Not Met ML20095J2261995-12-21021 December 1995 Revised TS Change Request 254,raising Low Voltage Action Level to 105 Volts DC ML20091L2831995-08-23023 August 1995 Rev to TS Change Request 223 to License DPR-50,incorporating Ref to 10CFR20.1302 ML20087F4881995-08-11011 August 1995 Rev to TS Change Request 252 to License DPR-50,removing TS Section 3.2 Re Makeup,Purification & Chemical Addition Sys Requirements.Certificate of Svc Encl ML20086R3001995-07-24024 July 1995 Rev to LAR 250 to License DPR-50,clarifying Section III, SE Justifying Change for source-range Nuclear Instrumentation SRs ML20085N1551995-06-22022 June 1995 TS Change Request 227 to License DPR-50,replacing Pages for App A.Certificate of Svc Encl ML20084N3461995-06-0101 June 1995 TS Change Request 223 to License DPR-50,deleting Remaining Portions of RETS & Relocating TSs Per Guidance in GL 89-01 & NUREG-1430 ML20084L4201995-06-0101 June 1995 TS Change Request 251 to DPR-50,revising TS 5.3.1.1 to Describe Use of Advanced Clad Assemblies ML20084B3261995-05-24024 May 1995 Application for Amend to License DPR-50.Amend Would Change Surveillance Test Requirements for source-range Nuclear Instrumentation ML20083N7771995-05-17017 May 1995 Application for Amend to License DPR-50,consisting of Change Request 252,removing Chemical Addition Sys Requirements from TS to COLR ML20079A7771994-12-23023 December 1994 Rev to TS Change Request 221 to License DPR-50,revising TS Page 3-32a ML20073F9241994-09-26026 September 1994 LAR 246 to License DPR-50,revising License Condition 2.C.9 Re Long Range Planning Program ML20069A6731994-05-20020 May 1994 TS Change Request 244 to License DPR-50,requesting Revised CR Trip Insertion Time Testing Acceptance Criterion for Remainder of Cycle 10 for 12 Specific CRs Which Initially Experienced Slow Rod Drop Times During Testing on 940317 ML20065M6681994-04-19019 April 1994 TS Change Request 237 to License DPR-50,deleting Audit Program Frequency Requirements from TS & Relocating Subj Requirements to Operational QA Plan ML20065K0381994-04-11011 April 1994 TS Change Request 238 to License DPR-50,relocating Detailed Insp Criteria,Methods & Frequencies of Containment Tendon Surveillance Program to FSAR ML20073C7701994-03-22022 March 1994 Application for Amend to License DPR-50 Re TS Change Request 242 Concerning Control Rod Trip Insertion Time Testing ML20064J3771994-03-11011 March 1994 Application for Amend to License DPR-50,revising TS Re Allowable Outage Time for Emergency Feedwater Pumps During Surveillance Activities 1999-08-20
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20211D1321999-08-20020 August 1999 Application for Amend to License DPR-50 to Revise TS Bases Re Degraded Undervoltage Relay Setpoint Calibration Frequency & Degraded Voltage Relay Tolerance Rev ML20210J0941999-07-29029 July 1999 Suppl TS Change Request 274 to License DPR-50,revising ESF Sys Leakage Limits in post-accident Recirculation Surveillance Tss,As Result of NRC Generic Concerns Re CR Habitability Issues ML20209D6651999-07-0808 July 1999 Corrected TS Pages 3-21,4-5a,4-9,4-38 & 6-3 to Amends 211 & 212 to License DPR-50.Pages Failed to Reflect Previously Approved Changes Granted in Amends 203 & 204 in Case of Amend 211 & 207 in Case of Amend 212 ML20196K5901999-06-29029 June 1999 LAR 285 for License DPR-50,clarifying Authority in Encl License Pages to Possess Radioactive Matls Without Unit Distinction,So That After Transfer of TMI-1 License to Amergen,Radioactive Matls Can Continue to Be Moved ML20209C0551999-06-29029 June 1999 LAR 77 for License DPR-73,clarifying Authority in Encl License Pages to Possess Radioactive Matls Without Unit Distinction,So That After Transfer of TMI-1 License to Amergen,Radioactive Matl May Continue to Be Moved ML20195E3341999-06-0404 June 1999 TS Change Request 265 to License DPR-50,modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20209B5891999-05-26026 May 1999 LAR 281 to License DPR-50,revising TMI-1 UFSAR Chapters 5 & 14 to Permit Use of Conservative Deterministic Failure Margin Methodology for Seismic Analysis of Portions of Auxiliary Steam Line.Rept 240046-R-001 Encl.Rept Withheld ML20206R1111999-05-13013 May 1999 Application for Amend to License DPR-50,requesting That License Sections 2.a.(3) & 2.c.(7) & TS Section 3.1.1 Be Revised to Incorporate Administrative Updating & Changes to Bases Statement ML20205H0691999-04-0101 April 1999 TS Change Request 262 to License DPR-50,revising TS by Adding LCO Action Statements & Making SRs More Consistent with NUREG-1430,correcting Conflicts or Inconsistencies Caused by Earlier TS Revs & Revising SFP Sampling ML20203B0421999-02-0202 February 1999 TS Change Request 274 to License DPR-50,expanding Scope of Systems & Test Requirements for post-accident RB Sump Recirculation ESF Systems & Increasing Max Allowable Leakage of TS 4.5.4 for Applicable Portions of ESF Systems ML20196H9751998-12-0303 December 1998 LAR 279 to License DPR-50,reflecting Decrease in RCS Flow Resulting from Revised Analysis to Allow Operation of Plant with 20% Average Level of SG Tubes Plugged Per SG ML20196G4401998-12-0303 December 1998 LAR 278 to License DPR-50,requesting Consent to Transfer & Authorize Amergen to Possess,Use & Operate TMI-1 Under Essentially Same Conditions & Authorizations Included in Existing License.Supporting Documentation,Encl ML20196G7671998-11-25025 November 1998 TS Change Request 277 to License DPR-50,changing Surveillance Specs for OTSG ISIs for TMI-1 Cycle 13 RFO Exams Which Would Be Applicable for One Cycle of Operation Only ML20195C6811998-11-12012 November 1998 Amend 52 to License DPR-73,relocating Audit Frequency Requirements from TMI-2 to TMI-2 Post Defueling Monitored Storage QA Plan & Extends Max Allowed Interval Between Certain Audits from 12 Months to 24 Months ML20154P8441998-10-19019 October 1998 Application for Amend to License DPR-50,providing Allowable RCS Specific Activity Limit Based on OTSG Insp Results Performed Each Refueling Outage.Proprietary & non- Proprietary Calculation,Encl.Proprietary Info Withheld ML20154Q6201998-10-19019 October 1998 TS Change Request 248 to License DPR-50,adding Operability & SRs for Remote Shutdown Sys Similar to Requirements in NUREG-1430, Std Tech Specs - B&W Plants, Section 3.3.18, Remote Shutdown Sys ML20154M3691998-10-15015 October 1998 Application for Amend to License Amend Request 276 to License DPR-50 Revising UFSAR Chapter 14 Accident Analysis Atmospheric Dispersion Factors.Ufsar Revised Pages Encl ML20249B2391998-06-11011 June 1998 TS Change Request 273 to License DPR-50,incorporating Alternate High Radiation Area Control Consistent W/Reg Guide 8.38 ML20217E5131998-03-23023 March 1998 Application for Amend to License DPR-50,revising TS Section 3.1.2 to Incorporate New Pressure Limits for Reactor Vessel IAW 10CFR50,App G for Period of Applicability Through 17.7 Efpy.Request Also Submitted in Response to NRC ML20217G0161997-10-0303 October 1997 Suppl to License Amend Request 268 to License DPR-50, Replacing Pages 4-80 & 4-81 Previously Submitted w/TMI-1 License Amend Request 268 on 970812 ML20211C2221997-09-19019 September 1997 Supplemental Application for Amend to License DPR-50 Re TS Change Request 266.Supplement Provides for Phased Review & Issuance of License Amends & Involves Administrative Correction to TS Decay Heat Removal Sys Leakage Rate ML20211C3211997-09-19019 September 1997 Supplemental Application for Amend to License DPR-50 Re License Amend Request 269 Submitted on 970814.Suppl Includes Addl Change to TS Section 3.1.4 & Proposed Page Rev Clarifying That UFSAR Analysis Is More Conservative ML20210J9951997-08-14014 August 1997 Revised License Amend Request 269 for License DPR-50, Revising TMI-1 UFSAR Section 14.1.2.9 Environ Dose Consequences for TMI-1 Steam Line Break Analysis ML20141J3981997-08-12012 August 1997 Tech Spec Change Request 268 for License DPR-50,revising Surveillance Specification for Once Through Steam Generator Inservice Insp for TMI-1 Cycle 12 Refueling (12R) Exams Applicable to TMI-1 Cycle 12 Operations ML20198E7871997-07-30030 July 1997 TS Change Request 266 to License DPR-50,incorporating Addl Sys Leakage Limits & Leak Test Requirements for Systems Outside Containment Which Were Not Previously Contained in TS 4.5.4 ML20141E1311997-05-0808 May 1997 Application for Amend to License DPR-50,consisting of Change Request 264,incorporating Addl NRC-approved Analytical Methods Used to Determine TMI-1 Core Operating Limits ML20140E2351997-04-21021 April 1997 Application for Amend to License DPR-50,requesting Rev to TS 3.3 Re Emergency Core Cooling,Reactor Bldg Emergency Cooling & Reactor Bldg Spray Systems ML20134M1111997-02-0707 February 1997 Application for Amend to License DPR-50,incorporating Certain Improvements from Revised STS for B&W Plants, NUREG-1430 & Addl Changes as Described in Encl TS ML20133D2651996-12-24024 December 1996 Application for Amend to License DPR-50,requesting Reinstatement of Auxiliary & Fuel Handling Bldg Ventilation Sys TS ML20132F3221996-12-16016 December 1996 Application for Amend to License DPR-50,consisting of Change Request 260,reflecting Change in Legal Name of Operator of Plant from Gpu Corp to Gpu Inc & Reflecting Plant License & TS Registered Trade Name of Gpu Energy ML20135C5201996-12-0202 December 1996 TS Change Request (Tscr) 75 to License DPR-73,relocating Audit Frequency Requirements to Pdms QA Plan ML20134D7761996-10-24024 October 1996 Amend 51 to License DPR-73,revising TS to Extend Surveillance Interval for Demonstrating Operability of Containment Airlock ML20128K1831996-10-0808 October 1996 Amend 50 to License DPR-73,revising TS to Incorporate Improvement from Administrative Controls Section of Revised STS for B&W Plants ML20117H0181996-08-29029 August 1996 Application for Amend to License DPR-50,consisting of TS Change Request 257,incorporating Certain Improvements from STS for B&W Plants (NUREG-1430) ML20113D1901996-06-28028 June 1996 Application for Amend to License DPR-50,consisting of Change Request 259,allowing Implementation of Recently Approved Option B to 10CFR50,App J ML20112C8751996-05-24024 May 1996 Errata to Application for Amend to License DPR-50,consisting of TS Change Request 243,replacing Pages for App a ML20101R1361996-04-10010 April 1996 Application for Amend to License DPR-50,consisting of Change Request 243,revising Addl Group of Surveillances in Which Justification Has Been Completed Following Receipt of 930623 Application ML20100J6831996-02-22022 February 1996 Application for Amend to License DPR-50,consisting of Change Request 254,revising Proposed TS Page 4-46 on Paragraph 4.6.2 That Provides Addl Testing Requirements in Case Station Battery Cell Parameters Not Met ML20095J2261995-12-21021 December 1995 Revised TS Change Request 254,raising Low Voltage Action Level to 105 Volts DC ML20091L2831995-08-23023 August 1995 Rev to TS Change Request 223 to License DPR-50,incorporating Ref to 10CFR20.1302 ML20087F4881995-08-11011 August 1995 Rev to TS Change Request 252 to License DPR-50,removing TS Section 3.2 Re Makeup,Purification & Chemical Addition Sys Requirements.Certificate of Svc Encl ML20086R3001995-07-24024 July 1995 Rev to LAR 250 to License DPR-50,clarifying Section III, SE Justifying Change for source-range Nuclear Instrumentation SRs ML20085N1551995-06-22022 June 1995 TS Change Request 227 to License DPR-50,replacing Pages for App A.Certificate of Svc Encl ML20084N3461995-06-0101 June 1995 TS Change Request 223 to License DPR-50,deleting Remaining Portions of RETS & Relocating TSs Per Guidance in GL 89-01 & NUREG-1430 ML20084L4201995-06-0101 June 1995 TS Change Request 251 to DPR-50,revising TS 5.3.1.1 to Describe Use of Advanced Clad Assemblies ML20084B3261995-05-24024 May 1995 Application for Amend to License DPR-50.Amend Would Change Surveillance Test Requirements for source-range Nuclear Instrumentation ML20083N7771995-05-17017 May 1995 Application for Amend to License DPR-50,consisting of Change Request 252,removing Chemical Addition Sys Requirements from TS to COLR ML20079A7771994-12-23023 December 1994 Rev to TS Change Request 221 to License DPR-50,revising TS Page 3-32a ML20073F9241994-09-26026 September 1994 LAR 246 to License DPR-50,revising License Condition 2.C.9 Re Long Range Planning Program ML20069A6731994-05-20020 May 1994 TS Change Request 244 to License DPR-50,requesting Revised CR Trip Insertion Time Testing Acceptance Criterion for Remainder of Cycle 10 for 12 Specific CRs Which Initially Experienced Slow Rod Drop Times During Testing on 940317 1999-08-20
[Table view] |
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METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY d/b/a GPU ENERGY GPU NUCLEAR, Inc.
Three Mile Island Nuclear Station, Unit 2 Possession Only License No. DPR-73 Docket No. 50-320 License Amendment Request No. 77 COMMONWEALTH OF PENNSYLVANIA ) 1
) SS:
COUNTY OF DAUPHIN )
This License Amendment Request is submitted in support of Licensee's request to change Possession Only License No. DPR-73 for Three Mile Island Nuclear Station, Unit 2. As part of this request, the proposed replacement page for the License is also included. All statements l contained in this submittal have been reviewed, and all such statements made and matters set forth !
therein are true and correct to the best of my knowledge.
i y , hw BY:
Vice President and Director, TMI Sworn and subscribed before me this day of_du n ,1999.
/$22Y~
Notary Public unew s Unda L RIter, Notary Put$c MyCommission Me 26 2002
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9907090059 990629 PDR ADOCK 05000320 p PDR
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l Enclosure 1 TMI-2 License Amendment Request 77 Safety Evaluation and No Significant Hazards Consideration l
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_1920-99-20335 Enclosure 1
~ Page l'of 3 I. LICENSE AMENDMENT REOUEST NO. 77 GPU Nuclear requests that the following change be made to the existing TMI-2 License:
A. Replacement page:
License page 3 II. REASON FOR CHANGE AND MARKUP OF CHANGES The purpose of this request is to clarify the authority to possess radioactive materials without unit distinction, so that aRer the transfer of the TMI-l license to AmerGen, radioactive materials may continue to be moved between the TMI-l and TMI-2 units as they currently are. Currently, while GPU Nuclear is the common licensee of TMI-l and TMI-2, TMI-2 License conditions 2B(4) and
- 2B(5) allow movement of radioactive materials between the units and common facilities, including staging of contaminated apparatus used at either unit and temporary staging of radioactive material generated by the units. In fact, PDMS SAR Section 7.1.3.1 states "the Fuel Handling Building may be utilized for the temporary staging of site-generated radwaste or other appropriate uses."' However, discussions with the NRC have suggested that, upon the TMI-l license transfer to AmerGen, these license conditions should be amended to make it clear that mJioactive materials may still be possessed without unit distinction at TMI aRer the license transfer.
The following are some examples of TMI-1 radioactive materials which would be staged or moved within TMI-2. Currently GPU Nuclear is planning to replace the internals package on a TMI-l reactor coolant pump during the upcoming 13R refueling outage. Because ofload handling and contamination control considerations, the spent fuel pool area in the TMI-2 Fuel Handling Building is the desired location for storing the used internals package. Additionally, plans are being made to purchase a used, contaminated reactor coolant pump motor as a TMI-l spare. The desired storage location for this spare motor would also be the TMI-2 spent fuel pool area. The process of handling contaminated protective clothing and radwaste includes temporarily staging these materials in the TMI-2 facility. Also, liquid radwaste processing
' involves movement between the units.
The requested changes are summarized as follows:
A. License condition 2B(4):
This paragraph is modified to allow GPU Nuclear to receive contaminated apparatus and components to be used at either TMI-l or TMI-2. This paragraph applies only to apparatus and components to be used at either facility and does not allow receipt and storage of radioactive waste from other sites.
B. License condition 2B(5):
This paragraph is modified to allow GPU Nuclear to possess radioactive material in
( TMI-l or TMI-2 which is produced by either unit.
l92,0-99-20335 Enclosure 1 Page 2 of 3 License page 3 Mark-up (4) GPU Nuclear Corporation, pursuant to the Act and 10 CFR Parts 30,40, and 70, to receive, possess., and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form, for i sample analysis or instrument calibration or associated with radioactive apparatus or components to be used at either TMI-1 or TMI-2; and (5) GPU Nuclear Corporation, pursuant to the Act and 10 CFR Parts 30,40, and j 70, to possess at the TMI Unit 1 or Unit 2 sites, but not separate, such {
byproduct and special nuclear materials whielHfemain O! the facility Subsequent l tc the c!canup fol!cwing the March 28,1979, accident-as may be produced by either unit.
III. S AFETY EVALUATION JUSTIFYING CHANGE The existing TMI-2 license conditions do not limit GPU Nuclear's authority to possess )
radioactive materials used or generated at TMI-2, and it is generally understood that this authority )
allows the possession of these materials at the TMI Station (i. e. at either unit and common facilities). As stated earlier, the PDMS SAR Section 7.1.3.1 anticipates the Fuel Handling Building being used for stagL g of" site-generated radwaste." However, as a result of discussions with the NRC staff, it has been decided to request a revision of the TMI-2 license to confirm the ,
continued permissibility of current practices associated with the movement and storage of j radioactive materials on the TMI site, following the TMI-l license transfer.
The handling and processing of contaminated clothing and radwaste has always been done using common processes and facilities at the TMI Station. Thus, radioactive materials generated at TMI-l and TMI-2 are temporarily stored at and moved between the units (including common facilities that will be part of TMI-l after the license transfer), under the control of TMI radioactive material handling procedures. Staging of contaminated apparatus and equipment at either unit is also a common practice. Typically, decisions on locations for staging radioactive material have considered factors associated with accessibility, load handling capability, environment, and ALARA.
These changes only make it clear that GPU Nuclear is authorized to receive and/or possess radioactive materials that are associated with maintaining TMI-2 or TMI-1. There is no intent of changing or expanding of past practices associated with the staging of radioactive materials.
IV. NO SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS Applying the three standards set forth in 10 CFR 50.92, the proposed changes to the licensee and Technical Specifications involve no significant hazards consideration. The proposed changes would:
E 1920-99-20335 Enclosure 1 l Page 3 of 3 l l a. - Not involve a significant increase in the probability of an accident previously evaluated because no accident initiators or assumptions are affected. The proposed changes have no effect on any plant systems. All Limiting Conditions for PDMS and Safety Limits specified in the Technical Specifications will remain unchanged.
Ib. Not involve a significant increase in the consequences of an accident previously evaluated because no accident conditions or assumptions are affected. The proposed changes do not alter the source term, containment isolation, or allowable radiological consequences. The staging of materials such as the contaminated reactor coolant pump and motor components will not result in a source term, that if released, would exceed that previously analyzed in the PDMS SAR in terms of off-site dose consequences. The proposed changes have no adverse effect on any plant system.
- 2. Not create the possibility of a new or different kind of accident from any accident previously evaluated because no new accident initiators or assumptions are introduced by the proposed changes. The proposed changes have no direct effect on any plant systems The changes do not affect any system functional requirements, plant maintenance, or operability requirements.
- 3. Not involve a significant reduction in the margin of safety because the proposed changes do f not involve significant changes to the initial conditions contributing to accident severity or consequences. The proposed changes have no direct effect on any plant systems.
Based upon the analysis provided herein, the proposed changes will not increase the probability or consequences of an accident previousi evaluated, create the possibility of a new or different kind of accident from any accident previously evaluated, or involve a reduction in a margin of safety.
Therefore, the proposed changes meet the requirements of 10 CFR 50.92(c) and involve no significant hazards consideration. I V. IMPLEMENTATION It is requested that the amendment authorizing this change become effective upon the TMI-1 sale closure and transfer date.
I
I Enclosure 2 TMI-2 License Revised Page f
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i B. . Subject to.the conditions and requirements incorporated herein, the Commission hereby licenses (1) GPU Nuclear Corporation, pursuant to Section 103 of the Atomic Energy Act
("Act") and 10 CFR Part 50, " Domestic Licensing of Production and Utilization Facilities," to possess but not operate the facility;
-(2) GPU Nuclear Corporation, Metropolitan Edison Company, Jersey Central Power and Light, and Pennsylvania Electric Company to possess the facility at the designated location in Dauphin County, Pennsylvania, in accordance with the procedures and limitations set forth in this license; l (3) GPU Nuclear Corporation, pursuant to the Act and 10 CFR Parts 31,40, and 70, to receive, possess, and use at any time any scaled sources for radiation monitoring )
equipment calibration; (4) GPU Nuclear Corporation, pursuant to the Act and 10 CFR Parts 30,40, and 70, I to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components to be used at either TMI-l or TMI-2; and l
'(5) GPU Nuclear Corporation, pursuant to the Act and 10 CFR Parts 30,40, and 70, to possess at the TMl Unit I or Unit 2 sites, but not separate, such byproduct and special nuclear materials as may be produced by either unit C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations in 10 CFR Chapter I, and is subject to all applicable prosisions of the Act arxl to the Commission's rules and regulations, except for those exemptions from specific portions of the regulations granted by the Commission and still applicable, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated bclow:
(1) Technical Specifications The Technical Specifications, as revised through Amendment No. 52, are hereby incorporated into this license. The licensee shall maintain the facility in accordance with the Technical Specifications and all Commission Orders issued subsequent to the date of the possession only license.
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i Enclosure 3 Certificate of Service for TMI-2 License Amendment Request No. 77 i
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- s UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF GPU NUCLEAR, Inc.
DOCKET NO. 50-320 LICENSE NO. DPR-73 4 CERTIFICATE OF SERVICE This is to certify that a copy of License Amendment Request No. 77 to the Possession Only License for Three Mile Island Nuclear Station Unit 2, has, on the date given below, been filed with executives of Londonderry Township, Dauphin County, Pennsylvania; Dauphin County, Pennsylvania; and the Pennsylvania Department of Environmental Resources, Bureau of 1 Radiation Protection, by deposit in the United States mail, addressed as follows:
1 Mr. Darryl LeHew, Chairman Ms. Sally Klein, Chairman ;
Board of Supervisors of- Board of County Commissioners i Londonderry Township of Dauphin County R.D. #1, Geyers Church Road Dauphin County Courthouse Middletown, PA 17057 Front & Market Streets i Harrisburg, PA 17101 Director, Bureau of Radiation Protection PA Department of Environmental Resources Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469 ;
ATTN: Mr. Stan T. Maingi )
GPU NUCLEAR INC.
BY:
Vice President and Director, TMI DATE: d 7/9f